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Thermal Aging of LAS Weld Metal from Decommissioned Nuclear Components in Swedish PWRs
Dept. of Maintenance, Analytical Services, Ringhals AB, SE-43285, Väröbacka, Sweden.
Dept. of Maintenance, Analytical Services, Ringhals AB, SE-43285, Väröbacka, Sweden.
KTH, School of Engineering Sciences (SCI), Engineering Mechanics, Vehicle Engineering and Solid Mechanics, Solid Mechanics. Dept. of Maintenance, Analytical Services, Ringhals AB, SE-43285, Väröbacka, Sweden.ORCID iD: 0000-0003-1498-5691
Dept. of Maintenance, Analytical Services, Ringhals AB, SE-43285, Väröbacka, Sweden; FS Dynamics Sweden AB, Mölndalsvägen 24, SE-41263, Gothenburg, Sweden.
2023 (English)In: Radiation Embrittlement Trend Curves and Equations and Their Use for RPV Integrity Evaluations, ASTM International , 2023, Vol. STP 1647, p. 204-216Conference paper, Published paper (Refereed)
Abstract [en]

Thermal aging has been considered a secondary aging and degradation mechanism for the low-alloy steels used in nuclear power plants. Given the relative interest in lifetime extensions, this has to be revised considering the extent of time at temperature during a 60-year operation time or even beyond. Traditionally, the effect has been coupled to the nonhardening effects caused by phosphorus and sulphur diffusion to available phase or grain boundaries, or both, resulting in a marked embrittlement of these low-alloy steels. This phosphorus segregation is proposed to be the main embrittlement mechanism for the weld metals investigated in this study. In the high-manganese/nickel/silicon-bearing weld metal used in both pressurizers (PRZs) and reactor pressure vessels (RPVs), some of the material extractions from the Ringhals power plant show a larger than expected effect from thermal aging, possibly by the formation of agglomerates in the matrix due to higher nickel content. Further, some of the tested materials showed a hardening effect after in-service exposure at temperature. The results presented here show that even though there are elements to be included in the fitness-for-service analysis of the power plants, with traditional prerequisites for the RPV it will be limited regarding the operating window. An empirically based embrittlement trend curve, related to thermal aging, for the PRZ will be developed after further testing of these materials.

Place, publisher, year, edition, pages
ASTM International , 2023. Vol. STP 1647, p. 204-216
Keywords [en]
aging analysis, embrittlement, pressurizer, reactor pressure vessel, thermal aging, trend curve
National Category
Metallurgy and Metallic Materials
Identifiers
URN: urn:nbn:se:kth:diva-335055DOI: 10.1520/STP164720220064Scopus ID: 2-s2.0-85166983937OAI: oai:DiVA.org:kth-335055DiVA, id: diva2:1793181
Conference
2022 Symposium on Radiation Embrittlement Trend Curves and Equations and Their Use for RPV Integrity Evaluations, Prague, Czechia, Apr 19 2022 - Apr 22 2022
Note

Part of ISBN 9780803177413

QC 20230831

Available from: 2023-08-31 Created: 2023-08-31 Last updated: 2023-08-31Bibliographically approved

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